ML19344F288
| ML19344F288 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crystal River  |
| Issue date: | 05/23/1980 |
| From: | Michelson C NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19344F281 | List: |
| References | |
| NUDOCS 8009150079 | |
| Download: ML19344F288 (2) | |
Text
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I MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
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Carl Michelson, Director Office for Analysis and Evaluation of Operational Data
SUBJECT:
LESSONS LEARNED FROM THE CRYSTAL RIVER TRANSIENT OF FEBRUARY 26, 1980 - CORRECTING ATMOSPHERIC DUMP VALVE OPENING UPON LOSS OF ICS PCWER At an April 24, 1980 meeting, Florida Power Corporation presented a list of items to be completed prior to restart of Crystal River Unit No. 3.
item, number 1.35, commits to:
One
" Provide override closure of atmospheric dump valves upon loss of ICS power."
Florida Power noted that the atmospheric dump valves on their plant open half-way upon ICS power failure.
Such a failure, coupled with an absence of atmos-pheric dump valve position, can significantly a which is initiated by a loss of NN1/ICS power. ggrevate an overcooling transient the meeting Floric. Power stated that they are planning to install ADV position indication which is powered by the NNI power supply.)
At that meeting, my staff as..ed whether or not the opening of the ADV's upon loss of ICS power is a design feature common to other B&W plants.
The B&W representatives (B. J. Short and E. Kane) indicated that they did not know.
My staff has reviewed Arkansas Power and Light Company's " Emergency Feedwater System Reliability Study," submitted to NRC on December 20, 1979.
It states that:
"The duenp valves fail to about 50% open on loss of control signal" (page 8).
It is not. clear to AE00 which other B&W plants have the same design deficiency, and whether or not they have reliable ADV position indication available to the operator.
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Harold R. Denton.
AE00 is in agreement with Florida Power that the aforementioned ADV design deficiency should be corrected expeditiously; however, the question of reliable ADV position indication has not, as yet, been addressed. AE0D requests that NRR take action to determine if the ADV design deficiency, which is apparent at Crystal River 3 and Arkansas One, Unit 1, is present al other plants, ano assure that this deficiency is correctea on a timely basis. AE00 also requests that NRR address the issue of the reliability of ADV position indication and its effect upon controlling the B&W plants during overcooling and undercooling transients.
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Carl Michelson, Director Office for Analysis and Evaluation of Operational Data cc:
D. Eisenhut
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T. Novak R. Reid D. Ross V. Stello R. Tedesco G. Lainas C. Berlinger E. Jordan AEOD Members
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